ML18142B244

LER 1976-027-00 for R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line

ML18142B244
Person / Time
Site:	Ginna
Issue date:	01/04/1977
From:	White L Rochester Gas & Electric Corp
To:	O'Reilly J NRC/IE, NRC Region 1
References
LER 1976-027-00
Download: ML18142B244 (12)

Text

NRC FORM 195 U.S. NUCLEAR REGULATORY C ISSION DOCKET NUMBER I2-76)

~4 50-244 FILE NUMBER NRC DISTRIBUTION FQR PART 50 DOCKET MATERIAL INCIDENT REPORT TO: FROM: GE DATE OF DOCUMENT ~

James P. 0" Reilly 1-4-77 Rochester N.X. 14649 Z,.D. White Jr. DATE RECEIVED 1-10-77 LETTE R 0 NOTOR IZE D PROP INPUT FORM NUMBER OF COPIES RECEIVED Q IP INAL NCLASSIFIED 30 copies OPY DEscRIP7IDN Ltr. Trans The Following: Licensee Event Report (RO-$ 0-244/76- 7) on 12<<16-76 concerning liqui> flowing through insulation on 2" let<azn <iversion line ue to pinhole leak between. pipe an< elbow...

D0 NOT REMOVE PLANT NAME: ROCHESTER G ACKNOWLFDGF~

R.E GINNA UNIT $ 1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION BRANCH CHIEF!

W 3 CYS FOR ACTION LIC", ASST' g CYS ACRS CYS +'

INTERNAL D ISTRI BUTION EG FI DR I6cE (2 MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL ISTR IBUTION CONTROL NUMBER LPDR!

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'e Uleto Docket Ite ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE. JR. 7 EL EPHI ON E VICE PRE5IOENT AREA COOE 7I5 546.2700 OOGREEED PSIIRC nuary 4, 1977 oI ~I~<II' CQ 6

V.S. IIVCEEAR REGlMTOR COMMISSION I Sodion

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Mr. James P. O'Reilly, r I5 U. S. Nuclear Regulatory Co on Office of Inspection and Enforcement Region I gag 631 Park Avenue g King of Prussia, Pennsylvania 19406

Subject:

Reportable Occurrence 76-27 (30-day report), Leak in letdown diversion line R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244

Dear Mr. O'Reilly:

In accordance with Technical Specifications, Article 6.9.2b, the attached report of Reportable Occurrence 76-27, 30-day, is hereby submitted. Two additional copies of this letter and the attachment are enclosed.

I Very truly yours, L. D. White, Jr.

Attachment cc: Dr. Ernst Volgenau (30)

Mr. William G. McDonald (3) r 2RP H

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LER 76-27/3L LICENSEE EVENT REPOR' CONTROL BLOCK: (PLEASE PAINT ALL AEOVIAED INFORMATION) 1 UCEN SEE EVENT NAME LICENSE NUMBER TYPE Qog N Y R E G 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~03 7 89 14 15 25 26 30 31 32 REPORT REPORT OOCKET NUMBER EVENT OATE REPORT CATE

~01 CON'T 0 0 2 4 4 1 2 1 6 7 6 0 1 0 4 7 7 7 '8 57 58 , 59 60 , 61 68 69 74 75 80 I

EVENT DESCRIPTION Qpg During normal rounds operator noticed liquid coming through insulation on.2" letdown.

7 8 9 80 diversion line., Upon return to steady state letdown condition, line was isolated.

7 89 80 t00j4 (Reportable Occurrence 76-27, .30-day) .

7 8 9 80 COOM 7~ 8'9 80 Ioag 7 8 9 FAME 80,

'YSTEM CAUSE COMPONENT COMPONENT COBE COOE COMPONENT CODE SUPPLER MANUFACTURER VCULTKIN Pop> ~CG. ~B P I P E X X ~N K 0 5 5 N 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION COOM A pinhole leak was found in socket weld between pipe and elbow. Weld was built up 7 8 9

[opg] in area of leak, and a visual inspection performed upon return of system to service ver80 7" 89 Qqg ified leak was stopped. This section-of line will be (cont'd. under Additional Factors), 80I 7 89 80 FACIUTY METHOO OF STATUS 55 POWER OTHER STATUS DISCOVERY OISCOVERY OESCRIPTION 7

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~E ~io 10'2 o NA b Operator making rounds 13 44 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

@~3 B ~d NA NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION

~3 ~OO O ~B NA 7 89 11 12 13 80 PERSONNEL INJURIES

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~0~0 0 NA 7 89 11 12 80 OFFSITE CONSEQUENCES

. ~15 ,NA 7 89 80 LOSS OR DAMAGE TO FACILITY, TYPE OESCRIPTION K~1 L~I NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIONAL FACTORS 'I Q~g (cont'd. from. Cause Description) replaced at next refueling shutdown to remove weld 7 89 80

.which had been leaking. CAR 1111 was issued to document this corrective action.

7 .89 80 ames Witte/D. Hamelink PHDNE 7 1 6 546 2700, ext ~ 29 1-2 1 S GPO dd'I 667

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U,S. NUCLEAR REGULATORY CO SION DOCKET NUMBER NRCyonM 195 I2.70 4~

I~~ O-244 FILF. NUMBER NRC DISTRIBUTION FoR PART 60 DOCKET MATERIAL INCIDENT REPORT TO: FROM: 'GE DATE OF DOCUMENT I

James P. 0 ReilXy Hochester N.Y. 146II9 12 6 L.D. White Jr. DATE RECEIVED 12-2 - 6

%LETTER ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED

@ORIGINAL )A[UNC LASS I F I E D 1 co~

gSjgOP Y DE c o Itr Hef their p8 19 76 ltr concer QGLosURE 23D Power Cabinet (Drop of Two Control ROIis)..

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DO NOT REMOVE ACKNOWLED(xED PLANT NAI,IE: H.E. GINNA .$ 1

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IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION cm 12-2 BRANCH CHIEF'- NCER W 3 CYS FOR ACTION LICo ASSTo P W CYS ACRS CYS HOLDING S NT INTERNAL DISTRIBUTION REG F g NRC PDR r I G,E 2 MIPC I SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY

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VOLLMER/BUNCH KREGER/J, COLLINS ons EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR:

TIC: 13024

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ROCIIESTER GAS AHD ELECTRIC CORPORATION ~ 89 EAST AVEHU -, ROCHESTER, N.Y. 14649 4

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LEON D. WHITE. JII ~

TCLIrPrrONF VICE PRESIDCNT RrrCR COOC 7Ir. 54G 2700 ~

> R '~~09'0Cf(et File December 2 1976r, Mr. James P. O'Reilly, Dire'c'tor U. S. Nuclear Regulatory Commission OI

"' ',,,. ~8Pe Office of Inspection and Enforcement Region I 651 Park Avenue King of Pru ssia, Pennsylvania 19406 (5l Subject Supplemental Report on Reportable Occu 6-21, Drop of Two Control Rods .

R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244

Dear Mr. O'Reilly:

In the August 19, 1976 Reportable Occurrence LER 76-21/3L it was stated that Westinghouse specialists assisted in the investigation of the problem with the 2BD power cabinet. Although no exact "ause could be iden-..

tified at that time, Westinghouse provided further recommendations for con-sideration. All these proposals were reviewed by the Ginna Station I & C Group and the PORC. EWR-1646 was issued for design review and safety analysis by the RG&E Engineering Department for these proposals, and they will be followed as conditions warrant.

Subsequently, the Westinghouse PWR Engineering Group has examined h

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and tested the fuses and sampling resistors which had been removed and reported that only one fuse had any sign of deterioration. It was determined that this would not have caused the dropped rod problem. Further, the sampling resistors could not be faulted. Two new recommendations concerning the

.sampling resistors will be carried out during the next refueling outage.

CAR 1082, issued previously for the investigation of the dropped rods associated with the 2BD Power Cabinet, remains in effect.

r Two additional copies of this letter are enclosed to conform to the original submittal of LER 76-21/3L.

Very truly yours, g':;,S.sP.

L. D. White, Jr.

cc: Dr. Ernst Volgenau (30)

Mr. William G. McDonald (3) 18024

hl AAP tOtt It ~P 'IIA'It ROCIIESTER GAS AND ELECTRIC CORPORATION o S9 EAST AVENUI"., ROCHESTER, N.Y. 14649 LEON D. WHITE. JH. TSLf P>1011F VICE PIIESIIIENT A1ISA COOL'14 5d6.2700 "

December 21, 1976 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Supplemental Report on Reportable Occurrence 76-21, Drop of Two Control Rods R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244

Dear Mr. O'Reilly:

In the August 19, 1976 Reportable Occurrence LER 76-21/3L it was stated that Westinghouse specialists assisted in the investigation of the problem with the 2BD power cabinet. Although no exact cause could be iden-tified at that time, Westinghouse provided further recommendations for con-sideration. All these proposals were reviewed by the Ginna Station I 6 C Group and the PORC. EWR-1646 was issued for design review and safety analysis by the RG6E Engineering Department for these proposals, and they will be followed as conditions warrant.

Subsequently, the Westinghouse PWR Engineering Group has examined and tested the fuses and sampling resistors which had been removed and reported that only one fuse had any sign of deterioration. It was determined that this would not have caused the dropped rod problem. Further, the sampling resistors could not be faulted. Two new recommendations concerning the sampling resistors will be carried out during the next refueling outage.

CAR 1082, issued previously for the investigation of the dropped rods associated with the 2BD Power Cabinet, remains in effect.

Two additional copies of this letter are enclosed to conform to the original submittal of LER 76-21/3L.

Very truly yours, cc: Dr. Ernst Volgenau (30)

Mr. William G. McDonald (3)

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